CAP1400压力容器外壁面临界热通量试验  

Test of Critical Heat Flux on Outer Surface of CAP1400 Pressurized Reactor Vessel

作　　者：史国宝 郑明光 张琨 匡波[2] 刘鹏飞[2] SHI Guobao;ZHENG Mingguang;ZHANG Kun;KUANG Bo;LIU Pengfei(Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd.,Shanghai 200233,China;School of Mechanical Engineering,Shanghai Jiao Tong University,Shanghai 200240,China)

机构地区：[1]上海核工程研究设计院有限公司,上海200233 [2]上海交通大学机械与动力工程学院,上海200240

出　　处：《上海交通大学学报》2022年第1期14-20,共7页Journal of Shanghai Jiaotong University

基　　金：国家科技重大专项资助项目(2018ZX06002004)。

摘　　要：根据模化原则建立了全高度切片型试验台架,采用爆炸焊技术研制了加热段,表面碳钢薄层可以真实模拟压力容器表面特性,开展了流道、压力、过冷度、流体水化学、表面状态等关键因素对压力容器外壁面临界热通量影响试验研究,获得了CAP1400压力容器外壁面传热极限规律,验证了熔融物堆内滞留措施中压力容器外流动和传热过程.A full height sliced test facility is established based on the modeling process.The heating test section is manufactured by adopting the explosive welding technology,and the surface of carbon steel can simulate the actual surface characteristic of a pressurized reactor.Critical heat flux tests on flow,pressure,subcooling degree,chemical material in water,and surface characteristics are performed on the outer surface of the pressurized reactor vessel.Therefore,the law of heat transfer limit on the outer surface of the CAP1400 pressurized reactor vessel is obtained,and the process of flow and heat transfer for in-vessel retention is validated.

关 键 词：压力容器外壁面 临界热通量试验 熔融物堆内滞留 

分 类 号：TL364[核科学技术—核技术及应用]